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if they are distributed exactly as the eigenfunction of the stationary problem. In the case of an arbitrary<br />

external source, this number becomes:<br />

⎛<br />

µ src<br />

= ν 1 ⎞<br />

⎜ −1<br />

⎟<br />

⎝ k src ⎠<br />

= ν<br />

M src<br />

−1<br />

The ratio:<br />

ϕ * = µ eff<br />

= 1− k eff<br />

µ src<br />

1− k src<br />

( )( k eff<br />

ν)<br />

( )( k src<br />

ν)<br />

is known as the importance of source neutrons. ν * is an effective number of neutrons per fission and<br />

thus contains a correction for non-fission multiplicative processes such as (n,Xn) reactions, which are<br />

of great importance for lead-bismuth or lead cooled fast reactors.<br />

The neutronic properties of three different source cases has been examined: a spallation source<br />

driven reference configuration (in short: reference or ADS case), a deuteron-deuteron fusion source<br />

case (D-D or DD) and a deuteron-triton fusion source case (D-T or DT). As compared with the<br />

reference case, the D-D configuration stayed within a range of 260 pcm (1 pcm = 1·10 -5 ) in terms of<br />

the neutron multiplication factor (k src ), cf. Table 3. The D-T source configuration exhibits a<br />

distinctively higher k src than the reference case, the difference in k src being 1 500 pcm (0.015). Other<br />

central neutronic parameters are shown in Table 4. It should be noted that the required fusion source<br />

intensities (“External n/s” in Table 4) are remarkably high. For comparison, it can be mentioned that<br />

the source intensity of large-scale inertial confinement fusion experiments reaches a level of ~10 18 n/s<br />

for the higher yielding D-T fusion.<br />

Table 3. Neutron multiplication factors for the different source configurations<br />

k eff<br />

k src<br />

ADS Fusion-DD Fusion-DT<br />

0.9634 0.9640 0.9614 0.9790<br />

Table 4. Main neutronic parameters for the different source configurations<br />

ADS Fusion-DD Fusion-DT<br />

ϕ* 1.0196 0.9478 1.7727<br />

M = 1/(1-k src<br />

) 27.8 25.9 47.6<br />

Total n/s 8.01 10 18 7.98 10 18 8.13 10 18<br />

External n/s 2.88 10 17 3.08 10 17 1.71 10 17<br />

fiss/s 2.50 10 18 2.50 10 18 2.50 10 18<br />

ν* 3.09 3.07 3.19<br />

σ capt<br />

(U 238 )/σ abs<br />

(Pu 239 ) 0.68 0.68 0.68<br />

Since the D-T source configuration case was found to show the most notable differences in<br />

comparison with the reference ADS case, the onus will be on comparing the reference ADS and D-T<br />

source configuration cases. In Table 5, the neutron balance of the whole EADF device is presented.<br />

The fuel core neutron balance is presented in Table 6.<br />

857

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